Análisis de termofluido y neutrónico de un reactor nuclear rápido enfriado con plomo
At present, energy demand grows as the population increases, it is estimated that in some decades fossil resources will not be enough to satisfy the demand. For this reason, many countries have been motivated to carry out research in design and develop for the application of energy alternatives like...
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| Tipo de documento: | dissertação |
| Estado: | Versão publicada |
| Data de publicação: | 2017 |
| País: | México |
| Recursos: | Universidad Autónoma Metropolitana |
| Repositório: | Repositorio Institucional de la UAM Iztapalapa |
| Idioma: | espanhol |
| OAI Identifier: | oai:bindani.izt.uam.mx:bz60cw251 |
| Acesso em linha: | https://doi.org/10.24275/uami.bz60cw251 |
| Access Level: | Acceso aberto |
| Palavra-chave: | info:eu-repo/classification/LEM/Reactores nucleares de plomo info:eu-repo/classification/LEM/Atomic energy info:eu-repo/classification/LEM/Nuclear lead reactors info:eu-repo/classification/LEM/Energía nuclear info:eu-repo/classification/cti/7 |
| Resumo: | At present, energy demand grows as the population increases, it is estimated that in some decades fossil resources will not be enough to satisfy the demand. For this reason, many countries have been motivated to carry out research in design and develop for the application of energy alternatives like solar, wind, biomass and nuclear. Within nuclear technologies, the Generation IV reactors (GIV) have been proposed. These reactors can help to satisfy energy demand while care the environment. For this reason, study and development of these reactors are important. The objective of this work was the development of a mathematical model that describes the phenomena of a lead-cooled fast reactor (LFR), which is classify as a GIV reactor. The analysis of neutron processes, heat transfer processes in the fuel rod and heat transfer processes in the coolant (thermofluid), were considered. This analysis allowed the development of a multi-physics and multi-scale model. For the neutron processes, was used neutron point kinetics model with six precursors of delayed neutrons, which considers effects of Doppler reactivity and expansion of nuclear fuel, including gap and clad expansion. The heat transfer model in fuel rod considers conduction of heat in fuel and clad, and considers also convection effects of gas gap and liquid lead. The thermofluid (coolant) in core was modeled from mass balance whit accumulation and convective effects, momentum balance and energy balance in transient and one-dimensional regime in direction of the mean fluid. Subsequently, the coupling step was carried out; where the processes are related from the variables they share (interactions between models). With the coupled model, numerical experiments were performed at steady state whit different power levels. Experiments were also carried out to analyze the transient behavior under conditions of loss of coolant, loss of reheaters and control bar drop (Insertion of positive reactivity). |
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